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Concept

Behavior of nuclear fuel during a reactor accident

Publications associées (28)

Development and Application of Data Assimilation Methods in Reactor Physics

Daniel Jerôme Siefman

Simulations of nuclear reactor physics can disagree significantly from experimental evidence, even when the most accurate models are used. An important part of this bias from experiment is caused by nuclear data. The nuclear data have inherent uncertaintie ...

EPFL2019

Application of causality analysis on nuclear reactor systems

Andreas Pautz, Hakim Ferroukhi, Abdelhamid Dokhane, Dionysios Chionis

Causality analysis is a substantial tool for identifying cause-and-effect links between different components of a system and has been extensively used in various areas of science such as neuroscience, climatology, and econometrics. This analysis is carried ...

American Institute of Physics2019

On benchmarking of simulations of particle transport in ITER

Olivier Sauter, Javier García Hernández, Federico Alberto Alfredo Felici, Francesca Maria Poli, Xiao Yuan, Anna Teplukhina

We report results of benchmarking of core particle transport simulations by a collection of codes widely used in transport modelling of tokamak plasmas. Our analysis includes formulation of transport equations, difference between electron and ion solvers, ...

IOP Publishing Ltd2019

Statistical Burnup Distribution Of Moving Pebbles In Htr-Pm Reactor

Andreas Pautz, Fanny Vitullo, Horst-Michael Prasser

In the pebble-bed high temperature reactor under construction in China, called HTR-PM, the spherical fuel elements continuously flow downward in the cylindrical core. After the discharge, the burnup of each pebble is checked at the core outlet and, accordi ...

AMER SOC MECHANICAL ENGINEERS2018

Modelling of fuel fragmentation, relocation and dispersal during Loss-of-Coolant Accident in Light Water Reactor

Vladimir Vladimirov Brankov

Recent LOCA tests with high burnup fuel at the OECD Halden Reactor Project and at Studsvik demonstrated the susceptibility of the fuel to fragment to small pieces, to relocate and possibly cause a hot-spot effect and to be dispersed in the event of claddin ...

EPFL2017

Investigation of the thermal conductivity of SiC/SiC cladding before and after irradiation

Loïc Guillaume Fave

Silicon carbide based composites are candidates for structural components and fuel claddings in nuclear power plants. In the frame of accident tolerant fuel research, the effective through-thickness thermal conductivity of SiC/SiC prototype claddings is in ...

EPFL2017

Overview of ASDEX Upgrade results

Olivier Sauter, Basil Duval, Stefano Coda, Timothy Goodman, Federico Alberto Alfredo Felici, Cristian Sommariva, Laurie Porte, Antoine Pierre Emmanuel Alexis Merle, Haomin Sun, Yann Camenen, Marco Wischmeier, Nicola Vianello, Alberto Bottino, Emiliano Fable, Andrea Scarabosio, Doohyun Kim, Dávid Wágner, Thomas Binderup Jensen

The ASDEX Upgrade (AUG) programme is directed towards physics input to critical elements of the ITER design and the preparation of ITER operation, as well as addressing physics issues for a future DEMO design. Since 2015, AUG is equipped with a new pair of ...

IOP Publishing Ltd2017

Neutronics modeling of the CROCUS reactor with SERPENT and PARCS codes

Andreas Pautz, Mathieu Hursin, Daniel Jerôme Siefman, Adolfo Rais

This paper reports the methodology used for the neutronic modelling of the CROCUS reactor and discusses the challenges encountered during the process. Full-core steady-state neutronics solutions were computed with the PARCS code. The Serpent Monte Carlo co ...

2017